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Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 1 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit.

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Presentation on theme: "Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 1 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit."— Presentation transcript:

1 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 1 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Status of accident analysis for HCPB X. Jin, L.V. Boccaccini, R. Meyder Garching, 9th Oct Meeting on Safety assessment for EU TBM

2 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 2 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit PIE HCS + CPS TES Plasma Chamber Port Cell TCWS vault T Building 1.A double-ended pipe break in the TBM cooling loop in a large diameter pipe (ID=100mm) of the primary loop discharging coolant in the TCWS vault during plasma burn. 2.The coolant inventory is lost and the heat removal capability of the HCS goes to zero in short time.

3 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 3 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Ex-vessel LOCA using RELAP5 MOD3.2 Double-ended pipe break in the TBM cooling loop in a large diameter pipe (DN100, Di=98.3mm, Da=114.3mm) during plasma burn (270KW/m²). Valve cross section: Vlve606 pipe break: m² (=2*pipe area) Pressure vessel (PV) vlve 702: m²

4 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 4 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Pressure results for ex-vessel LOCA time constant 1.05s (p=2.96MPa) at 2.4s p< 1MPa at 10s p 0 (time for ramp of HTC in the next calculation)

5 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 5 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Heat up of the FW (and TBM) HCS + CPS TES Port Cell TCWS vault T Building Hot spot 500KW/m² 270KW/m²

6 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 6 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Break of the FW HCS + CPS TES Plasma Chamber Port Cell TCWS vault T Building

7 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 7 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case A 3.A trigger system able to shut down the plasma in 100s is assumed and doesnt fail. 4.In this case, only the failure of the FW channels (now filled with a mixture of He/air at about 0.1 MPa) is considered as following failure; it opens a by pass from the TCWS to the VV with air penetration in VV. Be/air reaction at the FW surface occurs. 5.A loss of off-site power occurs, which is equivalent to a loss of heat sink in the TBM cooling system; it also means that the VV cooling system is in the natural convection mode. 6.After differential pressure inversion the gases (air, He) in the VV and in TBM flow towards outside through the TBM cooling loop bypass and tritium and dust can be transported from the gas stream and released in the external zones.

8 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 8 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit TBM-Model for study of temperature (air oxidation) Cut from EM_TBM (pol*tor*rad=740*1270*750) Boundary conditions: Surface heat flux 500/270KW/m² FW cooling 330°C, 5000W/m²K Cooling plate 450°C, 3000W/m²K Radial power distribution Radiation MF back side to 135°C Radiation after plasma off from Be- cover to blanket FW surface temperature* Radiation from BU back plate to MF3 Be reaction rate** After heating power factor * FIGURE VII G84RI R1.0 ** G81RI W0.1

9 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 9 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case A/3,4,5 (Other possibilities tbd)

10 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 10 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case A 100s delay (500KW/m²) Be-cover surface Plasma side interface FW2FW3FW4FW5FW Time (s) Temperature (°C) s 760

11 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 11 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case B 3.The detection of the ex-vessel LOCA fails to trigger the Fusion Power Shutdown System (FPSS); the plasma reaction runs until the beryllium cover of the first wall reaches 1290 °C. This is the melting temperature of beryllium and leads to inherent plasma shut down. 4.In this case it is assumed a complete failure of the FW integrity with penetration of air in the VV. 5.In addition it is assumed that a major plasma disruption is triggered by the entering air but without failure of water confinement in the shielding blanket or divertor system. 6.A loss of off-site power coincides with the disruption, which is equivalent to a loss of heat sink in the TBM cooling system; it also means that the VV cooling system is in the natural convection mode. 7.Box structures containing lithium orthosilicate and beryllium pebbles can loose their integrity. This means that air can enter the TBM box reacting with the Be pebbles. 8.After differential pressure inversion the gases (air, He) in the VV and in TBM flow towards outside through the TBM cooling loop bypass and tritium and dust can be transported from the gas stream and released in the external zones.

12 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 12 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case B/3,4,5,6,7

13 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 13 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case B 212s delay to Be melting point (270Kw/m²) Be-cover surface Plasma side interface FW2FW3FW4FW5FW Time (s) Temperature (°C) s 896

14 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 14 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case B/7 0.1MPa air in pebble bed (unrestricted air access model) Pebble bed temperatures, 24h after plasma offPebble bed temperatures, enlarged Temperature (°C) Time (h) Time (s) Temperature (°C)

15 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 15 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case C 5.In addition it is assumed that a major plasma disruption is triggered by the entering air with failure of water confinement in the shielding blanket or divertor system. 6.A loss of off-site power coincides with the disruption, which is equivalent to a loss of heat sink in the TBM cooling system; it also means that the VV cooling system is in the natural convection mode. 7.Box structures containing lithium orthosilicate and beryllium pebbles can loose their integrity. This means that a mixture of air/steam (tbd) can enter the TBM box reacting with the Be pebbles. 8.After differential pressure inversion the gases (air, steam) in the VV and in TBM flow towards outside through the TBM cooling loop bypass and tritium and dust can be transported from the gas stream and released in the external zones.

16 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 16 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case C Be/steam, assumption for ANSYS calculation Be+H2O->BeO+H2-370KJ/mol TBM pebble bed 0.2m³ Porosity por=0.67 steam diffuses into TBM pebble bed p max =60KPa, in =0.005mol/s m H2 Steam pressure in pebble bed p=nRT/[0.2*(1-por)], R=8.314J/molK

17 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 17 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit Case C Be/steam reaction 172g H2 generated after 5h, extrapolation to 1day 825.6g H2, 4days 3.3Kg H2 (tbd) g H2 generated after 5h, extrapolation to 1day 1.133g H2, 4days 4.53g H2 (tbd).

18 Forschungszentrum Karlsruhe in der Helmholtz-Gemeinschaft X. Jin & L.V. Boccaccinislide # 18 PL FUSION FZK - EURATOM ASSOCIATION Institut für Reaktorsicherheit tbd Case A/3 ramp of power for plasma shut down in 100s? Case A/6, B/8 After differential pressure inversion the gases (air, He) in the VV and in TBM flow towards outside through the TBM cooling loop bypass and tritium and dust can be transported from the gas stream and released in the external zones. Case B/3 reference temperature uses EUROFER melting point instead of Be melting point? Case C/7-8 Box structures containing lithium orthosilicate and beryllium pebbles can loose their integrity. This means that a mixture of air/steam (tbd) can enter the TBM box reacting with the Be pebbles. After differential pressure inversion the gases (air, steam) in the VV and in TBM flow towards outside through the TBM cooling loop bypass and tritium and dust can be transported from the gas stream and released in the external zones.


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